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Journal Articles

Corrosion behavior of simulated high-level waste glass in the presence of calcium ion or metallic iron

Maeda, Toshikatsu; Watanabe, Koichi; Omori, Hiroyuki*; Sakamaki, Keiko; Inagaki, Yaohiro*; Idemitsu, Kazuya*

Genshiryoku Bakkuendo Kenkyu (CD-ROM), 21(2), p.63 - 74, 2014/12

Static leach tests were conducted for simulated HLW glass in CaCl$$_{2}$$/Ca(OH)$$_{2}$$ solutions to investigate the corrosion behavior of HLW glass under calcium-rich environments induced by cement based materials in geological repositories. Another series of leach tests were conducted in deionized water in the presence of iron to investigate the effects of iron over-pack on the glass corrosion. In Ca solutions, corrosion of the glass was inhibited during the test period compared to that in deionized water, while the corrosion was enhanced at the presence of iron. The enhancement of the glass corrosion was assumed to be accompanied with transformation of silica, a glass network former, into iron silicates.

JAEA Reports

Analysis of the radioactivity concentrations in low-level radioactive waste generated from JPDR facilities, 3

Yasuda, Mari; Tanaka, Kiwamu; Watanabe, Koichi; Hoshi, Akiko; Tsuji, Tomoyuki; Kameo, Yutaka

JAEA-Data/Code 2014-011, 59 Pages, 2014/08

JAEA-Data-Code-2014-011.pdf:16.84MB

Simple and rapid methods to evaluate the radioactivity concentrations are required to be established for the near surface disposal of radioactive wastes generated from research facilities at Japan Atomic Energy Agency. In order to establish the methods to evaluate the radioactivity concentrations of miscellaneous solid wastes generated from research and testing reactors, we collected and analyzed samples from miscellaneous solid wastes generated by the decommissioning of JPDR (Japan Power Demonstration Reactor). In the present paper, we summarized data about the radioactivity concentrations which accumulated by the analysis.

JAEA Reports

Analysis of the radioactivity concentrations in low-level radioactive waste generated from JPDR facilities, 2

Tanaka, Kiwamu; Yasuda, Mari; Watanabe, Koichi; Hoshi, Akiko; Tsuji, Tomoyuki; Higuchi, Hidekazu

JAEA-Data/Code 2013-008, 16 Pages, 2013/11

JAEA-Data-Code-2013-008.pdf:2.41MB

Simple and rapid methods to evaluate the radioactivity concentrations are required to be established for the near surface disposal of radioactive wastes generated from research facilities at Japan Atomic Energy Agency. In order to establish the methods to evaluate the radioactivity concentrations of miscellaneous solid wastes generated from research and testing reactors, we collected and analyzed samples from miscellaneous solid wastes generated by the decommissioning of JPDR (Japan Power Demonstration Reactor). In the present paper, we summarized data about the radioactivity concentrations which accumulated by the analysis.

Journal Articles

Development of high-grade VPS-tungsten coatings on F82H reduced activation steel

Tokunaga, Tomonori*; Watanabe, Hideo*; Yoshida, Naoaki*; Nagasaka, Takuya*; Kasada, Ryuta*; Lee, Y.-J.*; Kimura, Akihiko*; Tokitani, Masayuki*; Mitsuhara, Masatoshi*; Hinoki, Tatsuya*; et al.

Journal of Nuclear Materials, 442(1-3), p.S287 - S291, 2013/11

 Times Cited Count:11 Percentile:64.2(Materials Science, Multidisciplinary)

JAEA Reports

Analysis of the radioactivity concentrations in low-level radioactive waste generated from JPDR facilities

Hoshi, Akiko; Tsuji, Tomoyuki; Tanaka, Kiwamu; Yasuda, Mari; Watanabe, Koichi; Sakai, Akihiro; Kameo, Yutaka; Kogure, Hiroto; Higuchi, Hidekazu; Takahashi, Kuniaki

JAEA-Data/Code 2011-011, 31 Pages, 2011/10

JAEA-Data-Code-2011-011.pdf:1.7MB

Simple and rapid methods to evaluate the radioactivity concentrations are required to be established for the near surface disposal of radioactive wastes generated from research facilities at Japan Atomic Energy Agency. In order to establish the methods to evaluate the radioactivity concentrations of miscellaneous solid wastes generated from research and testing reactors, we collected and analyzed samples from miscellaneous solid wastes generated by the decommissioning of JPDR (Japan Power Demonstration Reactor). In the present paper, we summarized data (262 data) about the radioactivity concentrations of the 7 important nuclides ($$^{3}$$H, $$^{14}$$C, $$^{60}$$Co, $$^{59}$$Ni, $$^{63}$$Ni, $$^{90}$$Sr, $$^{137}$$Cs) which accumulated by the analysis.

Journal Articles

Rapid separation of alpha-emitting nuclides in radioactive waste

Hoshi, Akiko; Watanabe, Koichi; Fujiwara, Asako; Haraga, Tomoko; Kameo, Yutaka; Nakashima, Mikio; Takebe, Shinichi

Nihon Genshiryoku Gakkai Wabun Rombunshi, 7(3), p.177 - 185, 2008/09

The simple and rapid separation method was developed for actinides in the low-level radioactive waste. Extraction chromatographic columns were used for the separation of U, Np, Pu, Am, and Cm in the solution of the simulated solidified product and the simulated waste solution. In the investigation of separation procedure, it was tried to construct the scheme with the relatively non-corrosive reagents aiming to apply to the routine analysis of the radioactive waste. Recoveries and decontamination factors of actinides in the solution of simulated waste were high enough to determine of actinides in radioactive waste by alpha-spectrometry, mass spectroscopy. The time required of the separation operation was 2-3 hours. The chromatographic method was applied to analysis of actinide in actual waste solution, high recoveries and decontamination factors were obtained, which indicated that the extraction chromatographic separation method would be adopted as a simple and rapid separation method of actinide in waste.

Journal Articles

A Simple radioactivity determination technique by alpha-ray spectrometry for homogenous thick sample

Kameo, Yutaka; Fujiwara, Asako; Watanabe, Koichi; Kono, Nobuaki; Nakashima, Mikio

Nihon Genshiryoku Gakkai Wabun Rombunshi, 4(3), p.187 - 193, 2005/09

no abstracts in English

Oral presentation

Positron annihilation in vacancy-Cu complexes in Si

Fujinami, Masanori*; Watanabe, Kazuya*; Oguma, Koichi*; Akahane, Takashi*; Kawasuso, Atsuo; Maekawa, Masaki; Matsukawa, Kazuto*; Harada, Hirofumi*

no journal, , 

no abstracts in English

Oral presentation

Positron annihilation study of impurity gettering in Si

Akahane, Takashi*; Fujinami, Masanori*; Watanabe, Kazuya*; Oguma, Koichi*; Matsukawa, Kazuto*; Harada, Hirofumi*; Maekawa, Masaki; Kawasuso, Atsuo

no journal, , 

no abstracts in English

Oral presentation

Positron annihilation of gettering sites of Si

Fujinami, Masanori*; Watanabe, Kazuya*; Oguma, Koichi*; Akahane, Takashi*; Kawasuso, Atsuo; Maekawa, Masaki; Matsukawa, Kazuto*

no journal, , 

no abstracts in English

Oral presentation

Cu gettering to vacancies in Si studied by a positron beam

Kawasuso, Atsuo; Maekawa, Masaki; Fujinami, Masanori*; Oguma, Koichi*; Akahane, Takashi*; Watanabe, Kazuya*; Matsukawa, Kazuto*

no journal, , 

Transition-metals are ubiquitous in Si devices to degrade their properties. Gettering has proved effective to trap contaminants and it is important to study their interaction. Extended defects such as stacking faults and precipitates have been investigated by TEM and impurity profile is analyzed by SIMS. However, such a approach cannot afford us the interaction of them. PAS is a powerful tool to analyze the defects and their coupled elements. A Cz-Si wafer was implanted with 3MeV Si ions to dose of 1E+14/cm$$^{2}$$ and Cu ion implantation was done into the back side (200 keV, 1E+14/cm$$^{2}$$). Variable-energy positron beam was employed and coincidence Doppler broadening spectra were taken at 15 keV after sample annealing. Up to 500$$^{circ}$$C, no differences between with and without Cu ion implantation are found and the clustering of vacancies takes place. At 600$$^{circ}$$C, the profile is very similar to that for the bulk Cu. At 700$$^{circ}$$C, the trapped Cu are released and oxygen atoms are coupled with vacancy clusters.

Oral presentation

Simple determination method for $$^{99}$$Tc in radioactive waste arising from research facilities

Kameo, Yutaka; Ishimori, Kenichiro; Hoshi, Akiko; Watanabe, Koichi; Takahashi, Kuniaki

no journal, , 

no abstracts in English

Oral presentation

Development of high-grade VPS-coating of tungsten on plasma-facing materials with high heat load resistance

Tokunaga, Tomonori*; Watanabe, Hideo*; Yoshida, Naoaki*; Nagasaka, Takuya*; Kasada, Ryuta*; Ezato, Koichiro; Suzuki, Satoshi; Akiba, Masato

no journal, , 

Oral presentation

Radiochemical analysis in stagnant water in Fukushima-1 Nuclear Power Plant, 2; Analysis of Se-79, Sr-90, Tc-99

Yasuda, Mari; Watanabe, Koichi; Hoshi, Akiko; Tanaka, Kiwamu; Kameo, Yutaka; Katayama, Atsushi; Higuchi, Hidekazu

no journal, , 

Analytical methods were developed for determination of Se-79, Sr-90 and Tc-99 in stagnant water generated from Fukushima-1 Nuclear Power Plant. The recoveries of these elements were enough to determine the concentrations of Se-79, Sr-90 and Tc-99. The interference of beta emitter could not be found by beta spectrometry. The present method could be applied to stagnant water.

Oral presentation

Study on the radiochemical method in stagnant water in Fukushima-1 Nuclear Power Plant

Tanaka, Kiwamu; Yasuda, Mari; Watanabe, Koichi; Hoshi, Akiko; Katayama, Atsushi; Higuchi, Hidekazu; Kameo, Yutaka

no journal, , 

no abstracts in English

Oral presentation

Study on dissolution of vitrified waste under the existence of magnesium ion

Ichiki, Takahiko*; Kakuta, Kenya*; Watanabe, Koichi*; Maeda, Toshikatsu

no journal, , 

no abstracts in English

16 (Records 1-16 displayed on this page)
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